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Book/Report | FZJ-2016-05601 |
1988
Kernforschungsanlage Jülich GmbH, Zentralbiliothek, Verlag
Jülich
Please use a persistent id in citations: http://hdl.handle.net/2128/12625
Report No.: Juel-2200
Abstract: In this report the systematic classification of the ATWS has been undertaken by analogy to the considerations made for water-cooled nuclear reactors. The initiating events of ATWS and protection actions of safety systems resulting from monitoring of the system variables have been described. The main emphasis of this work is the analysis of the core dynamic consequences of scram failure during the anticipated transients. The investigation has shown that because of the temperature feedback mechanisms a temperature rise during the ATWS results in a seif-shutdown of the reactor. Further inherent safety features of the HTR - conditioned by thehigh heat capacity of the core and by the compressibility of the coolant - do effectively counteract an undesirable increase of temperature and pressure in the primary circuit. In case of the longöterm failure of the forced cooling and following core heatup, neutron physical phenomena appear which determine the reactivity behaviour of the HTR. They are, for instance, the decay of Xenon 135, release of the fission products and subsiding of the top reflector. The results of the computer simulations show that a recriticality has to be excluded during the first 2 days if the reactor is shutdown by the reflector rods at the beginning of the accident.
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